Neutron detector

ABSTRACT

A device having: a scintillator material, an optically transparent element containing a glass or polymer and gadolinium oxide, and one or more photomultiplier tubes adjacent to the scintillator material. The optically transparent element is surrounded by the scintillator material.

This application claims the benefit of U.S. Provisional Application No.61/180,955, filed on May 26, 2009 and U.S. Provisional Application No.61/291,159, filed on Dec. 30, 2009. The provisional applications and allother publications and patent documents referred to throughout thisnonprovisional application are incorporated herein by reference.

TECHNICAL FIELD

The present disclosure is generally related to neutron detection.

DESCRIPTION OF RELATED ART

Current programs to interdict nuclear weapons and/or special nuclearmaterials at international border crossings rely on radiation portalmonitors to detect the presence of such materials in various types ofvehicles and transport containers. Most of these radiation portalmonitors use plastic scintillator materials to detect gamma-rays.Plastic scintillators are attractive because they provide goodsensitivity and they are relatively low cost. However, the incidence offalse alarms due to naturally occurring sources of radiation andradiopharmaceuticals can be quite high. The inconvenience and costsassociated with responding to these false alarms can represent anunacceptably high burden on the interdiction programs.

Gamma-rays interact with plastic scintillators primarily by Comptonscattering and the energy distribution produced by a gamma ray is acontinuum of energies. The immediate consequence is that plasticscintillators cannot be used to perform spectroscopic measurements thatcould be used to distinguish naturally occurring sources of radiationfrom illicit sources of radiation. Other gamma-ray detection materials,such as doped sodium iodide and germanium, are needed to performspectroscopic measurements. Detection systems using these materials arevery expensive and require highly skilled operators. Since plasticscintillators cannot be effectively used for gamma-ray spectroscopy,their utility for detecting gamma-rays is typically limited to the grosscounting of gamma pulses. Methods have been recently proposed thatutilize the limited energy information contained in the Comptoncontinuum generated in plastic scintillators to provide some level ofdiscrimination (Ely et al., “Discrimination of Naturally OccurringRadioactive Material in Plastic Scintillator Material,” IEEE Trans Nucl.Sci., 51(4), 1672-1676 (2004); Ely et al., “The Use of Energy Windowingto Discriminate SNM form NORM in Radiation Portal Monitors,” Nucl.Instr. & Meth. Phys. Res. A, 560, 373-387 (2006)). Theseenergy-windowing methods attempt to combine the limited spectroscopicinformation that is present with the pulse counting information toimprove the differentiation of the background radiation sources and thetargeted radiation sources. However, the common difficulty shared byboth approaches is the inability to adequately account for the dynamiccharacter of the background signal. The background radiation levels andspectral shape can be significantly different for each vehicle thatpasses through a portal monitor.

Current thermal neutron detection technologies, including helium-3 andBF₃ proportional counters, and lithium-6 isotopically enriched dopedglasses, are very expensive. Detection applications, such as portalmonitoring, that require large area sensors are prohibitively expensive.

BRIEF SUMMARY

Disclosed herein is a device comprising: a scintillator material, anoptically transparent element comprising a glass or polymer andgadolinium oxide, and one or more photomultiplier tubes adjacent to thescintillator material. The optically transparent element is surroundedby the scintillator material.

BRIEF DESCRIPTION OF THE DRAWINGS

A more complete appreciation of the invention will be readily obtainedby reference to the following Description of the Example Embodiments andthe accompanying drawings.

FIG. 1 shows prompt gamma-rays from Gd-157 neutron capture.

FIG. 2 schematically illustrates the components of the neutron detectionapproach.

FIG. 3 shows a rendition of large area gamma/neutron detection panel: a)3-D view, b) top view showing a neutron interaction.

FIG. 4 shows a porous glass structure with greater than 50% pore volume.

FIG. 5 shows basic micelle structure with non-polar molecular structureson the inside of the bubble.

DETAILED DESCRIPTION OF EXAMPLE EMBODIMENTS

In the following description, for purposes of explanation and notlimitation, specific details are set forth in order to provide athorough understanding of the present disclosure. However, it will beapparent to one skilled in the art that the present subject matter maybe practiced in other embodiments that depart from these specificdetails. In other instances, detailed descriptions of well-known methodsand devices are omitted so as to not obscure the present disclosure withunnecessary detail.

Materials and a method for the detection of neutrons are disclosed. Thematerials and methods provide sensitivity to thermal neutrons, fastneutrons, and low energy γ-rays. The ability to discriminate betweensignals from natural radiation sources such as terrestrial gamma rayevents is provided. The methods may provide, at low cost, large areadetectors that combine neutron detection and γ-ray detection in a singlematerial.

The disclosed device may provide an improved technique for the detectionof special nuclear materials and provide for effective discriminationbetween illicit materials and naturally occurring radioactive materials.Instead of relying only on the detection of gamma-rays, the device usesmaterials and techniques for the detection of neutrons and gamma-rays ina single detector volume. Pulse height discrimination is used todifferentiate between signals due to illicit materials and those due tobackground radiation and other naturally occurring radiation sources.The approach may provide good sensitivity and low cost, similar toplastic scintillators, but significantly reduce the incidence of falsealarms, which is an improvement over plastic scintillator portalmonitors.

A component of the system may be a high-Z scintillator material that iscost effective to produce in large quantities. The high-Z scintillatormay be inherently sensitive to γ-rays and incorporates polymers whichwork as an effective neutron moderator. The incorporation of a naturalgadolinium layer (used for thermal neutron capture) sandwiched betweentwo large-area panels of the scintillator adds an effective neutrondetection capability. Unlike previous neutron detectors utilizinggadolinium, the high-energy prompt-capture γ-rays are used toeffectively differentiate the neutron signal from other γ-ray events.The new scintillator may provide γ-ray spectral resolution that isbetter than polyvinyl toluene (PVT) based plastic scintillators.

The system may include signal processing electronics to allow for thesimultaneous measurement of the pulse-height, pulse shape, and positionof events within the scintillating panel. The measurement of theseparameters will allow for real-time deconvolution of the signal, furtherimproving the discrimination of neutron from γ-ray events and theeffective signal-to-noise ratio.

Components of the device include, but are not limited to: 1) anoptically transparent glass or polymer that contains between 10% and 70%by weight gadolinium oxide; 2) said transparent glass or polymersurrounded by a scintillator material that a) efficiently detectsx-rays, γ-rays, electrons, and even neutrons, and b) potentiallymoderates fast neutrons; and 3) one or more photomultiplier tubes thatare used to detect the scintillation light. The Gd-doped glass can havea very large thermal neutron capture cross section (4.6×10⁴ barns, where1 barn=1×10⁻²⁴ cm²) so that a very thin layer of the material canessentially capture every thermal neutron that impinges upon it. Thiscomposite absorption cross section is primarily due to contributionsfrom two isotopes, ¹⁵⁵Gd and ¹⁵⁷Gd with thermal neutron cross sectionsof 56,200 b and 242,000 b, respectively. For every neutron captureevent, a total of about 8 MeV of energy is released in the form ofphotons and electrons which can be detected by the surroundingscintillator. The energy events near 8 MeV are well separated from theCompton scattering events due to the natural gamma-ray background. As aresult, pulse height discrimination can be effectively used to isolateevents that are due to neutron capture. Energy windowing can also beused for the low energy γ-ray signals. The incorporation of the Gd-dopedglass into the scintillator material provides a new capability to detectboth neutrons and γ-rays in the same detector volume.

The neutron capture efficiency can be estimated as a function of thelayer thickness according to the formula for neutron absorption in alayer: I=I_(o)e^(−Σx) where Σ is the macroscopic thermal neutronabsorption cross-section and x is the thickness of the layer. Themacroscopic cross-section is a product of the microscopic cross-sectionand the number density of the Gd. For a 68% concentration by weight ofGd ions to polymer, corresponding to 5×10²¹ Gd ions per cm³, a thicknessof 0.1 cm will stop 99% of the incident neutrons.

In traditional neutron activation analysis, a neutron is captured by anatom, the excited atom then decays back to the ground state with a knownhalf-life (on the order of seconds or longer), emitting gamma-rays inthe process. These gamma-rays are then detected and used to determinethe amount of material or activity in the sample. Unlike traditionalneutron activation analysis techniques that utilize long-lived excitedstates, the excited state lifetimes of all Gd-156 and Gd-158 excitedlevels are nanoseconds except for the Gd-156 level at 2137 keV which hasa lifetime of 1.3 μs. As a result, the decay to the ground state can beconsidered to be a prompt reaction. Approximately 8 MeV of energy isreleased in this prompt decay consisting primarily of photons that rangein energy from about 30 KeV up to about 7 MeV. The γ-ray decay spectrumis shown in FIG. 1 for Gd-158.

Gadolinium-based scintillators have traditionally not received muchinterest because all of the secondary emissions are low LET particles,most are in the same energy range of terrestrial γ-rays, and many of thehigh energy γ-rays produced escape from a thin scintillator withoutproducing much scintillation light. In the present device neutron eventsand terrestrial γ-rays may be distinguished in a manner similar toprinciples first outlined in Nuclear Radiation Detection, second editionby William J. Price, 1958, 1964, McGraw-Hill, Inc.

The very high energy released following Gd neutron capture can be usedto effectively differentiate between neutrons and photons. This energyis about 8.53 MeV in the ¹⁵⁵Gd capture event and 7.94 MeV in the ¹⁵⁷Gdevent. The low LET electron radiation can be easily captured in even arelatively thin slab of scintillator material. Most of the lower energyphoton radiation can be readily absorbed in scintillators of reasonablesize. In fact, all of the current detection techniques that utilizegadolinium as the neutron absorber rely on the low energy particles tocause scintillation (Bell et al., Gadolinium-Loaded Plastic and RubberScintillators, work supported by the U.S. Department of Energy undercontracts DE-AC05-84OR21400 and DE-AC05-96OR22464). The problem is thatthese scintillators are also sensitive to gamma-rays. These γ-rays causethe same light output and therefore cannot truly be distinguished fromneutron events. Therefore, applications for these types of detectors arelimited to scenarios where there is a significant thermal neutronpopulation (i.e. an intense neutron beam) compared to the gamma-raybackground, like thermal neutron radiography and neutron scatteringexperiments. Unfortunately, this is counter to the application ofdetecting weak neutron sources amongst much larger γ-ray backgrounds. Sothese types of neutron scintillator detectors will simply not work as aSpecial Nuclear Materials (SNM) detector or search tool and do not havesufficient volume to be an effective gamma-ray detector.

The majority of the energy from the prompt decay is released in the formof one or more γ-rays with a total energy of up to 7 MeV. This energy iswell above the energies associated with the natural terrestrial γ-raybackground (<3 MeV). So the key is to produce a scintillator materialthat can effectively absorb this energy while discriminating betweenneutron events and γ-ray events using pulse height discrimination.Although many of these high-energy γ-rays will not be fully absorbed inthe scintillator, the use of a high-Z scintillator will assure that asignificant fraction of the full γ-ray energy will be deposited.

In addition, many neutron capture or inelastic scattering events willalso contribute to the neutron signal since the neutron capture promptγ-rays (n,γ) and γ-rays from neutron inelastic scattering (n,n′) eventsare of sufficiently high energy to be detected above terrestrial γ-rayenergies. In fact, these types of products from neutron interactions arecurrently used by the DOE Triage program as confirmatory indicators whenneutron sources are present in a sample.

Algorithms can be developed that analyze the detector response andclassify the type of event based on a statistical analysis that takesinto account variations in background levels. The signal processing anddata analysis techniques are fairly straight forward and can beconsidered mature technologies. Current PVT based systems use energywindowing techniques to grossly define detected γ-ray energies. In itssimplest form, the algorithms can define the high energy events asneutron events, while the remaining lower energy portion of the energyspectrum is γ-ray events. Further energy windowing will be based on theultimate energy resolution of the detector.

Signal processing electronics can digitize the signal from thephotomultiplier tubes on an event by event basis. These waveforms can beprocessed in real-time for the simultaneous calculation of the totalenergy of event (pulse-height), pulse-shape (time response) and whetherit was a single or multisite interaction (position of the event). Thesimultaneous measurement and of these parameters may allow for real-timedeconvolution of the signal to more accurately extract the energy ofparticle interacting in the scintillator. With these parameters it maybe possible to differentiate between high energy γ-rays from internalneutron capture (Gd) and from externally neutron capture (othersources), further improving the understanding of the source of theradiation.

In addition, since the neutron moderation time in the panel is short(˜20-30 μsec) and the neutron capture in Gd is prompt, the signalprocessing electronics and algorithms can allow for coincidencecounting. Another novel feature of the scintillation panel and thesignal processing electronics is data acquisition in list mode. In listmode, the time of individual reactions within the panel is recorded.This then allows one to identify coincident γ-ray and neutron events.

Fission events (such as the spontaneous fission of SNM) simultaneouslyrelease many γ-rays and neutrons. With a large area detection panel,these can be detected and attributed to the same source (i.e. thespontaneous fission event). SNM can then be more reliably detected withvery low signal rates and smaller quantities of SNM can be detected.

FIG. 2 illustrates the basic operation and the components of the system10. In order to detect fast neutrons 15, such as those given off asdecay products of plutonium, a neutron moderator 20 may be included.When fast neutrons 15 enter the moderator 20 they have a highprobability of experiencing collisions that cause them to lose energy.Effective moderators may contain atoms with low atomic weights. Amaterial with a high concentration of hydrogen atoms is suitable. A slabof polyethylene may be used since polyethylene is composed of onlycarbon and hydrogen atoms, but a scintillator with a high concentrationof hydrogen atoms could additionally serve as a moderator material.

Fast neutrons 15 from a source, such as plutonium, impinge on thedetector assembly 10 and are thermalized by interaction with themoderator materials 20. The thermalized neutrons 35 diffuse through thescintillator material 25 and are captured with high efficiency by a thinlayer of glass or polymer 50 containing 10%-70% (including 60%) Gd₂O₃ inits natural isotopic abundance. Based on the Gd thermal neutron crosssection, effectively 100% of the impinging thermal neutrons may becaptured by a submillimeter thickness of gadolinium-doped glass having aconcentration of 30% gadolinium. The primary thermal neutron capturereaction products for ¹⁵⁵Gd and ¹⁵⁷Gd are high energy conversionelectrons and γ-rays 40 with a total energy release of about 8 MeV. Theγ-ray and secondary electron products are readily detected by thescintillator 25 that surrounds the gadolinium doped glass 50. The energyfrom the electrons and γ-rays is converted into a very large number ofscintillation photons 45 that are detected by the photomultiplier tube(PMT) 30. Both scintillator 25 and Gd glass layers 50 are opticallytransparent in order to allow passage of scintillation photons 45 to thephotomultiplier tube 30. One possible configuration of the device isshown in FIG. 3.

The scintillator may comprise a composite, high-Z scintillator materialto detect 100 keV to 10 MeV photons from external sources. High-Zmaterials contain an atom having an atomic number of at least 45. Thecharacteristics of the composite high-Z scintillator materials may allowspectroscopic features, including high energy peaks, to be resolved, asin expensive inorganic scintillators. Unlike conventional inorganicscintillators, the cost, ruggedness and simplicity of the materials canbe more like those of plastic scintillator materials. This is possiblebecause the different phases of the composite material possess theproperties that are characteristic of the each respective phase. Forexample, the high-Z scintillator materials can be composed of distinctorganic and inorganic phases. The inorganic, high-Z phase may be capableof stopping high energy photons and electrons. The surrounding organicscintillator phase may receive essentially all of the energy that isdeposited in the high-Z phase. This is due to the intimate contact withthe inorganic phase and the short distances (sub-micron scale) involved.The composite high-Z scintillators may thus provide spectroscopicinformation not seen with conventional plastic scintillators but atpotentially lower cost than that of conventional inorganic scintillatormaterials such as doped sodium iodide and cooled germanium.

The composite scintillator materials may operate largely by themechanisms of pair production and photoelectric effect rather than beingdominated by Compton scattering as in plastic scintillator materialsalone. The composite, high-Z scintillator materials may be capable ofproviding spectral resolution comparable to that of NaI since theeffective density of the composites can be as high as, or even higher,than that of NaI. The composite high-Z scintillator materials may alsoperform better than conventional high-Z scintillators that contain highconcentrations of heavy metals in solution with organic dyes. The heavymetals cause quenching of the luminescence from the organic dyes,lowering the overall efficiency of detection. Since the scintillator(organic) phase is distinct from the high-Z (inorganic) phase (althoughit is in intimate contact on a sub-micron scale), quenching of thescintillation due to the high Z atoms does not occur.

In one embodiment of the scintillator, a heavy-metal sol-gel glassframework is intercalated with an organic scintillator. Porous inorganicglasses using heavy metal ions such as lead, barium and lanthanum havebeen prepared using sol-gel methods (Brinker et al., “Sol-Gel Science”Academic Press, Chapt. 14 (1990)). Sol-gel materials begin as liquidsolutions of mixtures of metal-organic complexes. Addition of a smallamount of acid or base can catalyze a reaction between the metal-organiccomplexes that results in the formation of an extended network of metaloxide bonds. Over a period of hours, to several days, the reactionproceeds to the point that the liquid solution is transformed into astiff gel that consists of a very porous metal oxide network withsolvent contained within the pores. As the gel ages, solvent is expelledfrom the pores and the physical size of the gel mass decreases. Theratio of solid-to-pore volume can be controlled by the choice ofappropriate environmental conditions to yield the desired finalstructure. Any remaining solvent can be removed by a process known assuper-critical drying, or by solvent exchange. FIG. 4 is a photograph ofa dry porous glass structure with more than 50% void volume that we haveprepared using the techniques described above. In the dry state, thestructure is highly scattering and appears white. When the void volumeis filled with a liquid, such as water or an organic solvent, thestructure becomes more transmissive to light due to the reduction of therefractive index difference between the two phases, and is a suitablehost for dissolved dyes such as 2,5-biphenyloxazole (PPO) and1,4-bis(5-phenyloxazole-2-yl) (POPOP) as required for scintillatorapplications.

Sol-gel structures can be fabricated using metal ions with very high Z,such as lead and/or barium, in combination with titanium oxides to formlead titanate or lead barium titanate structures. These structures canbe fabricated having a range of void volumes (˜50% void volume, forexample). The sol-gel solvent can be removed from the metal oxidestructure using super-critical drying techniques. The void volume isrefilled with a liquid polymer precursor (monomer). An organic dye isdissolved in the monomer prior to infusion into the metal oxidestructure. Polymerization can be thermally induced or catalyzed at lowtemperature and the final product is a solid, metal oxide/polymermaterial. The density of lead titanate PbTiO₃ is 7.5 g/cm³. With a 50%solid fraction in combination with a 50% polymer fill with a density of1.5 g/cm³, the total density of the detector will be approximately(0.5×7.5)+(0.5×1.5)=4.5 g/cm³. This density is significantly higher thanthat of NaI at 3.67 g/cm³.

Lead titanate has a refractive index of 2.6 which is very high comparedto any solvent or polymer that could be used to host a luminescent dye.This index mismatch would lead to an unacceptable level of scatteringlosses. The refractive index can be reduced dramatically byincorporating selected rare earth ions into the matrix. Specifically,samarium and dysprosium, at a concentration of 6 mole % in leadtitanate, have been shown to reduce the refractive index toapproximately 1.6 (Iakovleva et al., Thin Solid Films 446, 50-53(2004)). The same index lowering effect has also been observed for otherrare earth ions including cerium, 0.73 b and ytterbium, 37 b. Based onthermal neutron capture cross section considerations, Ce may be a goodfirst choice, although the index lowering may be more substantial withYb. Polymers used for the dye host can be engineered to have an indexvery close to 1.6 using a variety of additives so that scattering lossescan be virtually eliminated.

In another embodiment, diiodomethane is combined with an organic dye.Diiodomethane (CH₂I₂) is one of the densest liquids available. Inaddition, iodine has a number of strong epithermal neutron resonancesbetween 20 eV and 1000 eV that can help to increase the effectiveneutron capture cross section of a detector. Although CH₂I₂ can be useddirectly as a solvent for many organic dyes, the presence of the iodinedramatically reduces the fluorescence efficiency of the dye due toenhanced intersystem crossing to nonfluorescent triplet states.Therefore, direct dissolution of the dye in CH₂I₂ is not useful. Inorder to effectively utilize the high Z aspect of CH₂I₂ in ascintillator a composite solution consisting of encapsulated luminescentdyes that are suspended in CH₂I₂ can be used. Dyes can be incorporatedinto sub-micron micelle structures that effectively isolate them fromthe surrounding solvent. Micelles are essentially like soap bubblesconsisting of a membrane with hydrophobic molecular structures on oneside of the membrane and hydrophilic molecular structures on the otherside of the membrane. For example, a detergent may be used to form themicelles. Depending on the nature of the solvent, the membrane will forma sub-micron dimension spherical bubble when dispersed in the solvent.In an aqueous solvent, the hydrophilic structures will be located on theoutside of the bubble. For a non-aqueous solution, the hydrophilicstructures will be inside of the bubble. By mixing a water soluble dyewith a micelle-forming liquid and then suspending and dispersing themicelles, the dye molecules can be effectively isolated from the iodineatoms in the solution (FIG. 5). In this way, the dye will exhibit normalfluorescence behavior upon excitation.

A third embodiment uses a composite polymer containing lanthanide ionsand luminescent dyes. In this approach, metal ions, such as cerium orlead, can be incorporated into a polymer, such as polyvinyl alcohol(PVA), at concentrations of up to 70% by weight to create an effectivehigh-Z matrix. This material is prepared as a concentrated liquidmixture of metal ions and PVA in water. The solution can be atomized toform micron-sized particles from which the water solvent evaporates andthe result is a sub-micron diameter, polymer encapsulated cerium salt. Asimilar procedure can be used with a luminescent dye co-dissolved withPVA or other polymer to form sub-micron particles of dye-doped polymer.These particles can be mixed together and hot-pressed to form solid,optically transparent structures that can efficiently guidescintillation light to an array of PMTs. The structures may be rods orsheets and may be formed to optimally guide the light to a detector.

The high energy signature associated with the thermal neutron reactionwith gadolinium is of considerably higher pulse height than thatrecorded for terrestrial gamma ray interactions, which are typically <˜3MeV. By setting a discriminator at about 3 MeV, the signals due toterrestrial γ-rays are separated from the neutron interactions. Mostneutron capture or inelastic scattering events (i.e., in detectorhousing and structural assemblies) may also contribute to the neutrondetection since the neutron capture prompt gamma rays (n,γ) and gammarays from neutron inelastic scattering (n,n′) events are typically ofsufficiently high energy to be detected above the high discriminationlevel. In addition, any iodine utilized in the detector assembly (forexample, within the scintillator) will also yield high pulse heightsignatures through resonance reactions with epithermal neutrons. Energywindowing techniques can also be used to analyze the signals with energy<3 MeV.

MCNPX (Monte Carlo N-Particle eXtended) calculations may be utilized tooptimize the geometry of each of the components of the detector assemblyin order to maximize the efficiency of detection of any particularsource neutron spectra. This includes optimizing the thickness of thehigh cross section Gd-glass sheet/film, the thickness of the compositehigh-Z scintillator material for gamma capture (and neutron moderationif appropriate), the thickness of any polyethylene moderator slab, andthe detector area. The background response is minimized by theaforementioned pulse height discrimination; only the relatively fewcosmic ray neutron events are registered.

The disclosed device may potentially provide for a number of advantages.It can use a hybrid scintillation material that exploits the propertiesof two or more components disposed in separate phases within thematerial. It may provide a large-area neutron sensing capability forpassive detection of weapons of mass destruction that employ fissionableplutonium materials. Portal monitors that employ the device may becapable of rapidly scanning boats, vehicles, aircraft, and transportcontainers for the presence of fissile plutonium materials. Fordetection of weapons of mass destruction that employ fissionable uraniummaterials, it may also provide a large-area neutron sensing capabilityfor use in those detection systems utilizing active interrogationtechniques.

The high doping concentrations of the Gd-doped glass can provide foressentially 100% thermal neutron capture in a thin layer of the glass.The Gd-doped glass may be manufactured using naturally occurringgadolinium oxide. Isotopically enriched gadolinium is not needed inorder to achieve a large thermal neutron cross section. As a result, thegadolinium-doped glass is much less expensive than other neutron sensingmaterials that must be isotopically enriched.

The high-Z scintillator materials may be low cost and manufacture oflarge-area detectors will be cost effective.

These materials are sensitive to gamma rays having a wide range ofenergies, unlike plastic scintillator materials. They contain asignificant fraction of organic materials containing hydrogen and carbonatoms, and can therefore effectively moderate fast neutrons.

Previous neutron detectors using gadolinium were unable to differentiateneutron signals from gamma-ray signals. The high-Z scintillatormaterials disclosed herein provide the ability to discriminate thecapture gamma rays and conversion electrons that are produced as aresult of the neutron capture reaction from other, unrelated gamma-rayevents. The high-Z scintillator materials will be capable of spectrallyresolving gamma ray signals. This is not possible using conventionalplastic scintillators.

Obviously, many modifications and variations are possible in light ofthe above teachings. It is therefore to be understood that the claimedsubject matter may be practiced otherwise than as specificallydescribed. Any reference to claim elements in the singular, e.g., usingthe articles “a,” “an,” “the,” or “said” is not construed as limitingthe element to the singular.

What is claimed is:
 1. A device comprising: a scintillator material;wherein the scintillator material is a solution of: diiodomethane; and aluminescent dye encapsulated in micelles dissolved in the diiodomethane;an optically transparent element comprising a glass or polymer andgadolinium oxide; wherein the optically transparent element issurrounded by the scintillator material; one or more photomultipliertubes adjacent to the scintillator material; and signal processingelectronics coupled to the photomultiplier tube that calculate the pulseheight of a signal from the photomultiplier tube.
 2. The device of claim1, wherein the optically transparent element comprises about 10 to about70 wt% gadolinium oxide.
 3. The device of claim 1, wherein the glass orpolymer comprises polyvinyl alcohol.
 4. The device of claim 1, furthercomprising: a neutron moderator adjacent to the scintillator material.5. The device of claim 4, wherein the neutron moderator comprisespolyethylene.
 6. A method comprising: positioning the device of claim 1at a neutron detection location; monitoring the output of thephotomultiplier tubes; and recording the detection of a neutron when theoutput exceeds a predetermined threshold.
 7. The device of claim 1,wherein the optically transparent element comprises about 30 to about 70wt% gadolinium oxide.
 8. The device of claim 1, wherein the opticallytransparent element comprises about 60 to about 70 wt% gadolinium oxide.